Hostname: page-component-76fb5796d-22dnz Total loading time: 0 Render date: 2024-04-26T11:18:43.525Z Has data issue: false hasContentIssue false
  • English
  • Français

Simfuel Leaching Experiments in Presence of Gamma External Source (60CO)

Published online by Cambridge University Press:  10 February 2011

J.A. Serrano ,
J. Quiñones ,
P.P. Díaz Arocas ,
J.L. Rodríguez Almazán ,
J. Cobos ,
J.A. Esteban  and
A. Martínez-Esparza
J.A. Serrano
Affiliation:
Departamento de Fisión Nuclear. CIEMAT. Avda. Complutense, 22.28040 Madrid. SPAIN
J. Quiñones
Affiliation:
Departamento de Fisión Nuclear. CIEMAT. Avda. Complutense, 22.28040 Madrid. SPAIN
P.P. Díaz Arocas
Affiliation:
Departamento de Fisión Nuclear. CIEMAT. Avda. Complutense, 22.28040 Madrid. SPAIN
J.L. Rodríguez Almazán
Affiliation:
Departamento de Fisión Nuclear. CIEMAT. Avda. Complutense, 22.28040 Madrid. SPAIN
J. Cobos
Affiliation:
Departamento de Fisión Nuclear. CIEMAT. Avda. Complutense, 22.28040 Madrid. SPAIN
J.A. Esteban
Affiliation:
ENRESA, C/ Emilio Vargas, 7.28043 Madrid. SPAIN
A. Martínez-Esparza
Affiliation:
ENRESA, C/ Emilio Vargas, 7.28043 Madrid. SPAIN
Get access

Abstract

One of the factors considered within the studies of performance assessment on spent fuel under final repository conditions is the effect of the radiation on its leaching behavior. Radiation from spent fuel can modify some properties of both solid phase and leachant and therefore it would alter the chemical behavior of the near field.

Particularizing in the effect of the radiation on the leachant, it will cause generation of radiolytic species that could change the redox potential of the environment and therefore may bring on variations in the leaching process.

In this work, the chemical analogue utilized was SIMFUEL (natural UO2 doped with non-radioactive elements simulating fission products) and the leachants selected were saline and granite bentonite waters both under initial anoxic conditions. To emulate γ radiation field of a spent fuel, leaching experiments with external 60Co sources in a irradiation facility (Nayade) were performed. Initial dose rate used was 0.014 Gy/s.

Preliminary results indicate that radiation produces an increase of the uranium dissolution rate, being the concentrations measured close to those obtained in oxic atmosphere without radiation field. In addition the solubility solid phases from experimental conditions were calculated, for both granite bentonite water and 5 m NaCl media.

On the other hand, a tentative approach to model the role of γ radiolysis in these SIMFUEL tests has been carried out as well.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 608: Symposium QQ – Scientific Basis for Nuclear Waste Management XXIII , 1999 , 61
Copyright
Copyright © Materials Research Society 2000

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1 Sunder, S., Shoesmith, D.W., Johnson, L.H., Wallace, G.J., Bailey, M.G. and Snaglewski, A.P. in Scientific Basis for Nuclear Waste Management X, edited by Bates, J. and Seefeldt, W.B. (Mat. Res. Soc. Symp. Proc. 84, Boston, 1986) 103–113.Google Scholar
2 Christensen, H., in Scientific Basis for Nuclear Waste Management XVI, edited by Abrajano, T. Jr, and Johnson, L. H. (Mat. Res. Soc. Symp. Proc. 212, Boston, 1990) 213–220.Google Scholar
3 Loida, A., Grambow, B., Geckeis, H. and Dressler, P., in Scientific Basis for Nuclear Waste Management XVII, edited by Murakami, T. and Ewing, R. C., (Mat. Res. Soc. Symp. Proc. 353, Kyoto, 1994) 577–584.Google Scholar
4 Cobos, J., Rondinella, V.V., Matzke, Hj., Martinez-Esparza, A., Wiss, T.. “Radiolysis effects on uranium realease under spent fuel storage conditions”. Presented at GLOBAL'99. 30 Agosto-2 Sept. 1999. Jackson Hole, Wyoming, USA.Google Scholar
5 CIEMAT specific procedure N° PR-X8-01 (1996).Google Scholar
6 Fuentes, J., private communication, CIEMAT (1997).Google Scholar
7 Lucuta, P.G., Verall, R.A.., Matzke, Hj., Palmer, B.J.. J. Nucl. Mater. 178, 48 (1991).Google Scholar
8 Garcia-Serrano, J., Serrano, J.A., Diaz-Arocas, P., Quiñones, J., and Almazan, J.L.R., in Scientific Basis for Nuclear Waste Management XIII, edited by Oversby, V.M. and Brown, P.W. (Mat. Res. Soc. Proc. 412, Pittsburgh, PA 1996), p. 229–240.Google Scholar
9 Serrano, J., Quiñones, J., Diaz, PP, Rodríguez, J.L., Cobos, J., Caravaca, C.. “Influence of redox potential on the dissolution behaviour of SIMFUEL”.Presented at Spent Fuel 98 Wokshop. The Vegas, Nevada. USA. 18-20 May 1998.Google Scholar
10 Wolery, T.J., EQ3NR A computer program for geochemical aqueous speciation -solubility calculations: Theoretical manual, user's guide and related documentation (version 7.0) (1992).Google Scholar
11 Parkhurst, D. L. “User's guide to phreeqc. A computer program for speciation, reaction-path, advective-transport, and inverse geochemical calculations” u.s. geological survey Water-Resources Investigations Report 95-4227 (1995)Google Scholar
12 , Grenthe et al. “Chemical Thermodynamics of Uranium”, edited by Wanner, H. and Forest, I., NEA-OCDE (1992).Google Scholar
13 Quiñones, J., Serrano, J.A., Arocas, P. Diaz, Rodríguez Almazán, J.L., Esteban, J.A., Esparza, A. Martinez. Ciemat Informe Técnico DFN/RA-03/SP-99 (1999).Google Scholar
14 Christensen, H., Sunder, S., Shoesmith, D.W.. J. of Alloys and Compounds 213/214, 93–99 (1994).Google Scholar
15 Christensen, H.. Presented at Spent Fuel Workshop 1999. Ontario Canada (1999)Google Scholar
16 Carver, M.B., Hanley, D.V., Chaplin, K.R.. Maksima Chemist. A program for mass action kinetics simulation by automatic chemical equation manipulation and integration by using Stiff techniques. AECL-6413. (1979)Google Scholar
17 Bruno, J., Cera, E., Duro, L., Pon, J., Pablo, J. de, Eriksen, T. SKB Technical Report TR–98–22 (1998)Google Scholar
18 Kelm, M. private communication (1998).Google Scholar
19 Kelm, M. Presented at Spent Fuel Workshop 1999. Ontario Canada (1999).Google Scholar